A5022338226- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Nuclear Physics and Applications
- Metal and Thin Film Mechanics
- Ionosphere and magnetosphere dynamics
- Laser-induced spectroscopy and plasma
- Diamond and Carbon-based Materials Research
- Radar Systems and Signal Processing
- Ion-surface interactions and analysis
- Advanced SAR Imaging Techniques
- CAR-T cell therapy research
- Microwave Imaging and Scattering Analysis
- Immunotherapy and Immune Responses
- Atomic and Molecular Physics
- Metallurgical Processes and Thermodynamics
- Antenna Design and Optimization
- Direction-of-Arrival Estimation Techniques
- Protein Structure and Dynamics
- Machine Learning in Bioinformatics
- Semiconductor materials and devices
Forschungszentrum Jülich
2015-2024
Fraunhofer Institute for Cell Therapy and Immunology
2021
VITA (Germany)
2021
Technical University of Munich
2005-2020
Royal Military Academy
2020
Max Planck Institute for Plasma Physics
2019
Max Planck Society
2004-2019
KTH Royal Institute of Technology
2000-2017
Osaka University
2017
Kyushu University
2009-2017
Progress, since the ITER Physics Basis publication (ITER Editors et al 1999 Nucl. Fusion 39 2137–2664), in understanding processes that will determine properties of plasma edge and its interaction with material elements is described. Experimental areas where significant progress has taken place are energy transport scrape-off layer (SOL) particular anomalous scaling, particle SOL plays a major role diverted plasmas main-chamber elements, localized mode (ELM) deposition on mechanism for ELM...
The interaction of plasma with the walls has been one critical issues in development fusion energy research. On hand, induced erosion can seriously limit lifetime wall components, while, on other eroded particles be transported into core where they lead to dilution and losses due radiation. Low-Z materials induce only small radiation but suffer from large physical sputtering rates. Carbon based addition chemically erosion. High-Z show significantly smaller losses. One main goals present...
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation long-term fuel retention. The (i) limiter and (ii) divertor configurations have been studied JET-ILW (JET Be first wall W divertor), compared those former JET-C carbon-based plasma-facing (PFCs)). For configuration, gross at contact point was determined situ by spectroscopy between 4% (Ein = 35 eV) more than 100%, caused...
The erosion of tungsten (W), induced by the bombardment plasma and impurity particles, determines lifetime plasma-facing components as well impacting on performance influx W into confined region. screening divertor transport in largely content core, but source strength itself has a vital impact this process. JET tokamak experiment provides access to large set erosion-determining parameters permits detailed description closest ITER one: (i) effective sputtering yields fluxes function energy...
The chemical erosion of carbon in interaction with a hydrogen plasma has been studied detail ion beam experiments, and yield values are available as function energy surface temperature.However, the conditions ITER divertor cannot be simulated by especially far flux is concerned.Therefore, joint attempt was made through EU Task Force on plasma-wall international tokamak physics activity involving seven different fusion devices simulators to clarify dependence.For each data point local were...
Mechanisms underlying the retention of fuel species in tokamaks with carbon plasma-facing components are presented, together estimates for corresponding tritium ITER. The consequential requirement new and improved schemes to reduce inventory is highlighted results ongoing studies into a range techniques removal rate ITER each case. Finally, an approach involving integration many operational schedule proposed as means extend period operations before major intervention required.
The effective sputtering yield of Be (Y tot ) was determined in-situ by emission spectroscopy low ionising as function the deuteron impact energy (E in = 25 -175eV and surface temperature (T surf 200 • C -520 C) limiter discharges carried out JET tokamak.Be self dominates erosion at high energies > 150eV causes Y far beyond 1.The drops to values, below 4.5%, accessible lowest ≃ 25eV achievable configuration.At medium energies, E 75eV , two contributors measured 9% were identified: third...
The Wendelstein 7-X (W7-X) optimized stellarator fusion experiment, which went into operation in 2015, has been operating since 2017 with an un-cooled modular graphite divertor. This allowed first divertor physics studies to be performed at pulse energies up 80 MJ, as opposed 4 MJ the phase, where five inboard limiters were installed instead of a This, and number other upgrades device capabilities, extension regimes higher plasma density, heating power, performance overall, e.g. setting new...
Abstract Results from three-dimensional modeling of plasma edge transport and plasma–wall interactions during application resonant magnetic perturbation (RMP) fields for control edge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The full 3D fluid kinetic neutral code EMC3-EIRENE is used modeling. Four characteristic perturbed topologies considered discussed with reference to axisymmetric case without RMP fields. Two field amplitudes at half ELM coil current...
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with ITER-like wall (ILW). global beryllium (Be) erosion deposition simulated compared experimental results from passive spectroscopy. For limiter configuration, it demonstrated that Be self-sputtering an important contributor (at least 35%) erosion. Taking this contribution into account, confirms previous evidence high deuterium (D) surface concentrations up ∼ 50% atomic...
Abstract The paper provides an overview of recent modelling global material erosion and deposition in the fusion devices Wendelstein 7-X (W7-X), JET ITER using Monte-Carlo code ERO2.0. For validating tool a three-dimensional environment, W7-X simulations are performed to describe carbon from graphite test divertor units, which were equipped operational phase OP 1.2 analysed post-mortem. Synthetic spectroscopy line emission is compared with experimental results spectrometer measurement...
Abstract We propose a machine‐learning approach to sequence‐based prediction of protein crystallizability in which we exploit subtle differences between proteins whose structures were solved by X‐ray analysis [or both and nuclear magnetic resonance (NMR) spectroscopy] those NMR spectroscopy alone. Because the technique is usually applied on relatively small proteins, sequence length distributions datasets adjusted avoid predictions biased size. As feature space for classification, used...
The first results of the Dynamic Ergodic Divertor in TEXTOR, when operating m/n=3/1 mode configuration, are presented. deeply penetrating external magnetic field perturbation this configuration increases toroidal plasma rotation. Staying below excitation threshold for m/n=2/1 tearing mode, rotation is always direction current, even if projection rotating opposite direction. observed consistent with a radial electric field, generated by an enhanced electron transport ergodic layers near...
Abstract Despite rapidly increasing numbers of available 3D structures, membrane proteins still account for less than 1% all structures in the Protein Data Bank. Recent high‐resolution indicate a clearly broader structural diversity initially anticipated, motivating development reliable structure prediction methods specifically tailored this class molecules. One important target capturing major aspects protein's is its contact map. Our analysis shows that computational trained to predict...
The ITER baseline scenario, with 500 MW of DT fusion power and Q = 10, will rely on a Type I ELMy H-mode, ΔW 0.7 MJ mitigated edge localized modes (ELMs). Tungsten (W) is the material now decided for divertor plasma-facing components from start plasma operations. W atoms sputtered targets during ELMs are expected to be dominant source under partially detached conditions required safe operation. impurity concentration in core can dramatically degrade its performance lead potentially damaging...
Abstract The three-dimensional Monte Carlo code ERO has been used to simulate dedicated DIII-D experiments in which Mo and W samples with different sizes were exposed controlled well-diagnosed divertor plasma conditions measure the gross net erosion rates. Experimentally, rate is significantly reduced due high local redeposition probability of eroded high- Z materials, according modelling mainly by electric field density within Chodura sheath. Similar ratios obtained from three sheath models...
The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring arising from assembly tolerances. This departure a perfectly cylindrical surface automatically leads magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide benchmark for series erosion/re-deposition simulation studies performed the FW panels, dedicated experiments have been on EAST tokamak using specially designed,...
The ITER baseline scenario, with 500 MW of DT fusion power and Q = 10, will rely on a Type I ELMy H-mode be achieved tungsten (W) divertor. W atoms sputtered from divertor targets during mitigated ELMs are expected to the dominant source in ITER. impurity concentration plasma core can dramatically degrade its performance lead potentially damaging disruptions. Understanding physics target due sputtering inter-ELMs is important helped by experimental measurements improved precision. It has...
Rate coefficients for the excitation and ionization of neutral as well singly ionized particles and-–predominantly-–their ratios S(D)/XB, which are important conversion photon into particle fluxes in ionizing fusion boundary plasma, have been modelled experimentally determined plasmas fusion-relevant species such He I, Li C B I&II, O Si Mo W H2, CH(D), C2.
Mater.415 S165-S169) carried out with the LIM code of ITER first wall (FW) on beryllium (Be) erosion, re-deposition and tritium retention by co-deposition under steady-state burning plasma conditions have shown that, depending input parameter assumptions sputtering yields, erosion lifetime fuel some parts FW can be a serious concern.The importance issue is such that benchmark this previous work sought has been provided ERO (Pitts et al 2011 J. Nucl.Mater.415 S957-S964) simulations described...